ML13092A346

Email, Acceptance Review, Relief Request ANO2-ISI-015, from Pressure Testing Requirements for Reactor Vessel Flange Seal Leak Detection Piping for the Fourth 10-Year Inservice Inspection Interval

ML13092A346
Person / Time
Site:	Arkansas Nuclear
Issue date:	04/02/2013
From:	Kalyanam N Plant Licensing Branch IV
To:	Clark R Entergy Operations
Kalyanam N
References
ANO2-ISI-015, TAC MF0941
Download: ML13092A346 (2)

Text

From: Kalyanam, Kaly To: CLARK, ROBERT W Cc: Lent, Susan; Burkhardt, Janet

Subject:

Result of the Acceptance Review on Request for Relief No. ANO2-ISI-015, to Entergy, Licensee for ANO-1 and 2

Date: Tuesday, April 02, 2013 1:12:46 PM SUNSI information:

Plant: Arkansas Nuclear One, Unit 2 Docket No.: 50/368

Subject:

Result of the Acceptance Review on Request for Relief No. ANO2-ISI-015, to Entergy, Licensee for ANO-1 and 2 TAC No.: MF0941 SUNSI Review Done: Yes. Publicly Available, Normal Release, Non-sensitive, From: R. Clark To: N. Kalyanam

Subject:

Acceptance of Arkansas Nuclear One - Unit 2; Request for Relief from from American Society of Mechanical Engineers (ASME) Code,Section XI - Request for Relief ANO2-ISI-015 (TAC No. MF0941)

Bob:

By letter dated March 1, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession umber ML12063A538), Entergy (the licensee) submitted Request for Relief (RR) No. ANO2-ISI-015, from the requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI, for Arkansas Nuclear One, Unit 2 (ANO, Unit 2). The relief pertains to the period pressure testing requirements for ANO-2 reactor vessel flange seal leak detection piping.

Entergy has determined that the required pressure test requirements are impractical due to the configuration and design of the system, and compliance with the specified requirements of this section would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety. The proposed alternative is based on ASME Code Case N-805, Alternative to Class 1 Extended Boundary End of Interval or Class 2 System Leakage Testing of Reactor Vessel Flange O-ring Leak Detection System.

Entergy also stated that during the next ANO-2 refueling outage (2R23), when the alternative examination method could be performed, will occur in Spring 2014 (fourth ISI 10-year interval, second period). Entergy plans to credit the 2R22 examination of the reactor flange seal leak detection system to the fourth ISI 10-year interval, first period, which began March 26, 2010, and will end March 25, 2013, should it comply with the relief request as approved by the NRC.

The purpose of this email is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff's acceptance review of this relief request. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant.

Pursuant to Sections 50.55a(a)(3)(i) and 50.55a(a)(3)(ii) of the Code of Federal Regulations (10 CFR), the applicant shall demonstrate that the proposed alternatives would provide an acceptable level of quality and safety, or that compliance with the specified requirements of Section 50.55a would result in hardship or unusual difficulty without a compensating increase in the level of quality or safety.

The NRC staff has reviewed your Request for Relief, ANO2-ISI-015, and concluded that it does provide technical information in sufficient detail to enable the staff to proceed with its detailed technical review and make an independent assessment regarding the acceptability of the proposed relief request in terms of regulatory requirements and the protection of public health and safety and the environment.

Given the lesser scope and depth of the acceptance review as compared to the detailed technical review, there may be instances in which issues that impact the NRC staffs ability to complete the detailed technical review are identified despite completion of an adequate acceptance review. If additional information is needed for the staff to complete its technical review, you will be advised by separate correspondence.

If you have any questions, please contact me at (301) 415-1480.

N (Kaly) Kalyanam Project Manager - ANO-2 US NRC/NRR/DORL/LPL4 kaly.kalyanam@nrc.gov 301-415-1480 DOCKET No. 50-368